ML17298B618

Confirms That Pump & Valve Operability Assurance Program for Unit 1 Complete W/Exceptions Noted in Encl Justifications for Interim Operation,Per Section 3.9.3.2 of SER (NUREG-0857)

ML17298B618
Person / Time
Site:	Palo Verde
Issue date:	12/10/1984
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0857, RTR-NUREG-857 ANPP-31416-EEVB, NUDOCS 8412120099
Download: ML17298B618 (18)

Text

REGULATO INFORMATION DISTRIBUTION TEM (RIDS)

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ACCESSION NBR;8412120099 DOC ~ DATE! 84/12/10, NOTARIZED: YES DOCKETACILISTN-.SO 528 Palo Verde Nuclear Station~

Unit 1 i Arizona Publ i 05000528 STN SO 529 Palo Verde Nuclear Station~

Uni,t 2~ Arizona Publi 05000529 STN-50. 530 Palo Verde Nuclear Station~

Unit 3i Arizona Publi

05000530, AUTH ~ NAME AUTHOR AFFILIATION VAN BRUNTiE,E.

Arizona Public Service Co.

'REC IP ~ NAME>

REC IPI ENT AFFILIATION KNIGHTONe G ~ < ~

Licensing Branch 3

SUBJECT:

Confirms that-pump,8 valve operability assurance

program, for'nit,l complete w/exceptions noted in encl Justifications'or inter im operation~per Section 3 ' '.2 of SER (NUREG 0857)

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DISTRIBUTION CODE:

B001D COPIES RECEIVED+LTR ENCL SIZE:

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TITLE: Licensing Submittal:.PSAR/FSAR Amdts

& Related Cor respondence NOTES:Standardized plant.

Standardized plant.

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05000S28 05000529 05000530 RECIPIENT ID CODE/NAME NRR/DL/AOL NRR LB3 LA INTERNAL: ACRS 41 ELO/HDS3 IE/DEPER/EPB "36 IE/OQASIP/QAB21 NRR/DE/AEAB NRR/OE/EHEB NRR/OE/GB 28 NRR/DE/MTEB 17, NRR/DE/SGEB 25 NRR/OHFS/LQB 32 NRR/OL/SSPB NRR/OSI/ASB NRR/OS I/CSB 09 NRR/DS I /METB 1?

NRR/DS I /RAB 22 LE 04

/MIB EXTERNAL: BNL(AMDTS ONLY)

FEMA REP DIV 39 NRC POR 02'T'I S

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1 RECIPIENT ID CODE/NAME NRR LB3 BC LICITRA E '1 ADM/LFMB IE FILE IE/DEPER/IRB 35 NRR ROEgM ~ L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/OHF$ /HFEB40 NRR/DHFS/PSRB NRR/OS I/AEB 26 NRR/DS I/CP8 10 NRR/DSI/ICSB 16 NRR/OS I/PSB 19 NRR/DSI/RSB 23 RGNS DMB/OSS (AMDT$)

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Arizona Public Service Company ANPP-31416-EEVB/t6'Q/Mt%

December 10, 1984 Director of Nuclear Reactor Regulation Attention: Yir. George W. Knighton, Chief Licensing Branch No.

3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Docket Nos. STN-50-528/529/530 Pump and Valve Operability Assurance Program File: 84-056-026; G.l.01.10

Reference:

NUREG-0857, Supplement No.

5 "Safety Evaluation Report" Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2 and 3, dated

November, 1983.

Dear Mr. Knighton:

As required by Section 3.9.3.2 of the referenced SER, Arizona Public Service hereby confirms that the Pump and Valve Operability Assurance Program for PVNGS-Unit 1 is complete with the exceptions noted in Attachment l.

Attachment 1 contains justification for interim operation for each item which is not expected to be completed prior to fuel load.

If you have any questions, please contact Mr. W.F. Quinn of my staff.

Very truly yours, EEVBJr/KEJ/no Attachment cc:

E.A. Licitra w/a H. Garg w/a A.C. Gehr w/a R.P.

Zimmerman w/a am~

E. E.

Van Brunt, Jr.

APS Vice President Nuclear Production ANPP Project Director 84i2i20099 84i2i0 E

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ANPP-31416 STATE OF ARIZONA

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COUNTY OF >fARICOPA)

I, Edwin E.

Van Brunt, Jr.,

represent that I am Vice President, Nuclear Production of Arizona Public Service

Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its

contents, and that to the best of my knowledge and belief, the statements made therein are true.

Edwin E.

Van Brunt, Jr.

Sworn to before me thia~Dday of dc 1984.

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My Commission Expires:

My CommIssion Expires April 6, 1987 otary Publ

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Attachment 1

Justifications for Interim Operation

PURCHASE ORDER NUMBER:

13-JM-601A DES CRIPTION:

Atmospheric dump valves PROJECTED DATE OF COMPLETION OF OPERABILITY ASSURANCE PROGRAM:

April 15, 1985 TAG NUMBER J-S GB-HV-178 J-S GB-HV-179 J-SGB-HV-184 J-SGB-HV-185 ENVI.

DESIG.*

SAFETY FUNCTION Decay heat removal for safe shutdown Same as above Same as above Same as above HISTORY:

During preoperational testing of the four (4) atmospheric dump valves (ADV), HV-178,

179, 184 and 185 it was observed that HV-178 behaved erratically.

Subsequent investigation revealed condensate buildup in the lines created excess force which damaged the internals of the valves.

All four (4) ADVs were disassembled, inspected and repaired.

JUSTIFICATION FOR INTERIM OPERATION:

Additional drain capability is being installed to remove condensate from the outlet port of the valve.

These valves will be tested prior to Unit 1 initial criticality.

The ADVs are not required to perform their safety function prior to initial criticality since no decay heat is present.

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PURCHASE ORDER NUMBER:

13-PM-221C DESCRIPTION:

Q-Class check valves PROJECTED DATE OF COMPLETION OF OPERABILITY ASSURANCE PROGRAM:

April 15, 1985 TAG %HfBER:

P-SGA-V887 ENVI.

DESIG.*

SAFETY FUNCTION Opens when steam flow is required to drive the steam turbine-driven auxiliary feedwater system pump P-SGA-V888 Same as above HISTORY:

During preoperational testing of the Auxiliary Feedwater

System, the Terry Turbine tripped on overspeed when starting

-from a cold, ambient condition (DER 84-51).

The solution to the problem was to make necessary design changes which included adding Q-class check valves V887 and V888 listed above.

Due to the unavailability of Q-class

valves, non-Q-class valves were installed to validate the design modification.

After successfully completion of the test Q-class valves became available and were installed.

JUSTIFICATION FOR INTERIM OPERATION:

The function of the check valves is to allow steam flow to the Terry Turbine which in turn drives the steam turbine-driven auxiliary feedwater system pump.

The testing of these check valves will be performed prior to Unit 1 initial criticality.

Prior to this time, these valves are not required to perform their safety function since there is no decay heat present.

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PURCHASE ORDER NUMBER:

DESCRIPTION:

PROJECTED DATE OF COMPLETION OF OPERABILITY ASSURANCE PROGRAM:

13-Bf-221B Anchor Darling air operated valve January 15, 1985 TAG NUMBER:

J-SGB-UV-130 J-SGB-UV-135 J-SGA-UV-172 J-SGA-UV-175 ENVI.

DESIG.*

SAFETY FUNCTION Close on MSIS II Close on MSIS II Close on MSIS II Close on MSIS HISTORY:

During preoperational

testing, these Anchor Darling supplied downcomer feedwater isolation valves failed to close fast enough due to the misdesign of the actuators (Refer to DER 84-66).

The modified actuators are being reinstalled under design change package 1SM-AF-500.

Due to the testing and documentation time involved, it is not ezpected that the operability assurance program for these valves will be complete prior to-issuance of the operating license.

JUSTIFICATION FOR INTERIM OPERATION:

The safety function of these valves is to isolate feedwater from the steam generators in the event of a

steam line break.

Testing will be complete prior to Post Core Hot Functional testing.

Accordingly, there will be no adverse safety consequences in granting a schedular exemption to January 15, 1985.

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PURCHASE ORDER NUMBER:

13-NM-001 TAG NUMBER:

P-SIA-V205 P-SIB-V206 DESCRIPTION:

ENVI.

DESIG.*

SAFETY FUNCTION III III Opens when in recirculation mode Same as above Containment sump return check valves PROJECTED DATE OF COMPLETION OF OPERABILITY ASSURANCE PROGRAtf:

April 15, 1985 HISTORY:

The containment sump check valves have not successfully passed required operability testing.

JUSTIFICATION FOR INTERIM OPERATION:

The function of the containment sump check valves is to open during the recirculation mode.

These valves will be tested prior to Unit 1 initial criticality.

These valves are not required to perform their safety function prior to initial criticality.

PURCHASE ORDER %BEER:

DESCRIPTION:

PROJECTED DATE OF COMPLETION OF OPERABILITY ASSURANCE PROGRAM:

13-JM-705 TAG NUMBER-J-ECA-XCV-15A J-ECA-XCV-15B J-ECB-XCV-16A J-ECB-XCV-16B J-ERA-XCV-89A J-ERA-XCV-89B J-EWB-XCV-90A J-EHB-XCV-90B ENVI.

DESIG.*

IV IV IV IV

. III Excess Flow Check valves SAFETY FUNCTION Close on rupture of downstream piping Same as above Same as above Same as above Same as above Same as above Same as above Same as above April 15, 1985 HISTORY:

The excess flow check valves have not succesfully passed required operability testing.

A JUSTIFICATION FOR INTERIM OPERATION:

I The excess flow check valves will be tested prior to Unit 1 initial criticality.

The excess flow check valves are not required to perform their safety function prior to initial criticality since no decay heat is present.

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NOTE-

• Environmental Designations (FSAR Section 3.11)

I P

Components Inside Containment The temperature,

pressure, humidity, and chemical environment inside containment after a LOCA or %ISLB.

II III Components inside containment which are required after a design basis LOCA.

r Components Outside Containment The expected temperature and humidity environmental conditions specified in appendix 3E of the PVNGS FSAR.

IV Components outside containment that are required to mitigate the consequences of a design basis LOCA.

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